Results 251 to 260 of about 744 (275)

Simulation Analysis of the Design of a Vacuum Pumping System for the Closed Helical Divertor in the Large Helical Device

open access: yesPlasma and Fusion Research, 2011
A promising candidate of a vacuum pumping system for the closed helical divertor in the large helical device is proposed using a three-dimensional neutral particle transport simulation code (EIRENE) and a finite element based multi-physics analysis ...
M Shoji, S Masuzaki, R Sakamoto
exaly   +3 more sources

Design and installation of the closed helical divertor in LHD

Fusion Engineering and Design, 2010
Abstract Neutral particle behavior in the Large Helical Device heliotron has been investigated to conduct the effective particle control using the intrinsic helical divertor. It was revealed that the torus in–out asymmetry observed in the neutral pressure distribution depended on the divertor particle flux distribution, and thus, on the operational ...
S Masuzaki, M Shoji, M Tokitani
exaly   +2 more sources

Study of a Closed Divertor Configuration for the Three-Dimensionally Complicated Magnetic Structure in the LHD Plasma Periphery

open access: yesPlasma and Fusion Research, 2008
The distribution of strike points in a closed divertor configuration with additional baffle plates installed in the toroidal ends of closed divertor components near lower/upper ports is calculated by tracing magnetic field lines from the last closed flux
M Shoji   +2 more
exaly   +3 more sources

Development of New Concept In-Vessel Cryo-Sorption Pump for LHD Closed Helical Divertor

open access: yesPlasma and Fusion Research, 2016
The in-vessel cryo-sorption pump for the Closed Helical Divertor (CHD) in the Large Helical Device (LHD) has been developed at the National Institute for Fusion Science (NIFS).
Takanori Murase   +2 more
exaly   +4 more sources

Simulation Analysis of Carbon Deposition Profile in the Closed Helical Divertor Configuration in the Large Helical Device

open access: yesContributions To Plasma Physics, 2016
0000-0003-0655-7347Recent long pulse plasma discharges in the Large Helical Device have been interrupted by radiation collapse induced by large amounts of dusts released from a closed divertor region.
M Shoji, G Kawamura, Hirohiko Tanaka
exaly   +3 more sources

The role of divertor pumping in plasma detachment and particle exhaust in a closed divertor

Nuclear Fusion, 2020
Abstract The impact of pumping on divertor power dissipation and particle exhaust in a closed divertor with flat target configuration is examined using SOLPS modeling. A closed divertor can increase neutral pressure and enhance radiative dissipation; accordingly it has been proposed as a direction for the design of advanced divertors to ...
Chaofeng Sang   +3 more
openaire   +1 more source

Observation of the Periodical Movement of Ionized Front in a Closed-Divertor Simulator.

open access: yesJournal of Plasma and Fusion Research, 2002
Takehisa Shibuya   +2 more
exaly   +3 more sources

Closed corner divertor with B × ∇B away from the divertor: a promising divertor scenario for tokamak power exhaust

Plasma Science and Technology, 2023
Abstract A major challenge facing the steady-state operation of tokamak fusion reactors is to develop a viable divertor solution with order-of-magnitude increase in power handling capability as compared with present experience. A recently developed divertor concept for this end has been tested recently on EAST tokamak through combining ...
Guosheng XU   +7 more
openaire   +1 more source

MAST upgrade closed pumped divertor design and analysis

Fusion Engineering and Design, 2011
Abstract The design of the Mega Amp Spherical Tokamak (MAST) Upgrade project provides an excellent opportunity for advancements in tokamak physics in support of ITER and DEMO as well as CTF. One of the main areas of contribution is the divertor. MAST Upgrade will be capable of operating with the outer leg of the divertor being either conventional or ...
G Fishpool, M Fursdon, V Thompson
exaly   +2 more sources

Comparison of open-closed divertor geometries in ASDEX

Journal of Nuclear Materials, 1990
Abstract Divertor impurity retention and exhaust capability were studied at ASDEX for two different divertor geometries. In one of these, bypass openings allow neutral gas exchange between divertor and main chamber (open divertor), in the other the bypasses are closed (closed divertor).
M Bessenrodt-Weberpals   +2 more
exaly   +4 more sources

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